Power Reactors (Division 1): Regulatory Guides 1.221 - 1.240
This page lists the number, title, publication date, and revisions for each regulatory guide in Division 1, "Power Reactors," with references to draft guides and related documents (where applicable).
See also Draft Regulatory Guides for Public Comment.
See NRC Regulatory Guides for more general information.
Regulatory Guides are reviewed about every 10 years, although a guide may be reviewed more frequently if the staff believes an emerging issue affects the guide. The NRC began these reviews in 2010, and began posting the results of its reviews on this site in 2013. The review dates are hyperlinked to the review memorandum, which provide useful information about the status and any known issues with the associated regulatory guide.
Guide | Title | Revision | Issue | Additional Information |
|---|---|---|---|---|
1.221 | Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants | 0 | ||
1.222 | Conducting Periodic Testing for Breakaway Oxidation Behavior | DG | ||
1.223 | Testing for Postquench Ductility | DG | ||
1.224 | Establishing Analytical for Zirconium Based Alloy Cladding | DG | ||
1.226 | Flexible Mitigation Strategies for Beyond-Design-Basis Events | 0 | ||
1.227 | Wide-Range Spent Fuel Pool Level Instrumentation | 0 | ||
1.228 | Integrated Response Capabilities for Beyond-Design Basis Events | DG | ||
1.229 | Alternative Risk-Informed Approach for Addressing the Effects of Debris on Post Accident Long-Term Core Cooling | DG | ||
1.230 | Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule | 0 | ||
1.231 | Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Safety-Related Applications for Nuclear Power Plants | 0 | ||
1.232 | Developing Principal Design Criteria for Non-Light Water Reactors | 0 | ||
1.233 | Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors | 0 | ||
1.234 | Evaluating Deviations and Reporting Defects and Noncompliance Under 10 CFR Part 21 | 1 | ||
0 | ||||
1.235 | Emergency Planning for Decommissioning Power Reactors | DG | DG-1346 , Rev 1, Proposed Revision 0 for RG 1.235 | |
1.236 | Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents | 0 | ||
1.237 | Guidance for Changes During Construction for New Nuclear Power Plants Being Constructed Under a Combined License Referencing a Certified Design Under 10 CFR Part 52 | 0 | ||
1.238 | Criteria for The Protection of Safety-Related (Class 1E) Power Systems and Equipment for Nuclear Power Plants | 0 | ||
1.239 | Licensee Actions to Address Nonconservative Technical Specifications | 0 | ||
1.240 | Fresh and Spent Fuel Pool Criticality Analysis | 0 |
Page Last Reviewed/Updated Monday, March 16, 2026
Page Last Reviewed/Updated Monday, March 16, 2026